slides - Generic Issue Management--An Idea Taking Flight
slides - Generic Issue Management--An Idea Taking Flight
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
In July 1999, the U.S. Nuclear Regulatory Commission (NRC) Spent Fuel Project Office
(SFPO) issued Interim Staff Guidance 8 Revision 1 (ISG8R1) to provide recommendations for the use
of burnup credit in storage and transport of pressurized-water reactor (PWR) spent fuel. Subsequent to
the issuance of ISG8R1, the NRC Office of Regulatory Research (RES) has directed an effort to
investigate the technical basis for extending the criteria and recommendations of ISG8R1 to allow
In the course of producing electrical power in light water.reactors (LWRs), the uranium
fuel accumulates fission products until the fission process is no longer efficient for power
production. At that point the fuel is removed from the reactor and stored in water basins
to allow radioactivity to partially decay before further disposition. This fuel is referred
to as "spent fuel." Although spent fuel as At is discharged from a reactor is intensely
radioactive, it has been stored safely in moderate quantities for decades. Spent fuel could
Utilization of burnup credit in criticality safety analysis for long-term disposal of spent
nuclear fuel allows improved design efficiency and reduced cost due to the large mass of fissile
material that will be present in the repository. Burnup-credit calculations are based on depletion
calculations that provide a conservative estimate of spent fuel contents (in terms of criticality
potential), followed by criticality calculations to assess the value of the effective neutron
The "Summary Report of Commercial Reactor Criticality Data for Davis-Besse Unit 1" contains the detailed information necessary to perform commercial reactor criticality (CRC) analyses for the Davis-Besse Unit 1 reactor.
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
This Plan outlines the Department of Energy’s (DOE) current strategy and planning for
developing and implementing the transportation system required to transport spent nuclear fuel
(SNF) and high-level radioactive waste (HLW) from where the material is generated or stored to
the proposed repository at Yucca Mountain, Nevada. The Plan describes how DOE’s Office of
Civilian Radioactive Waste Management (OCRWM) intends to develop and implement a safe,
secure and efficient transportation system and how stakeholder collaboration will contribute to
This topical report describes the approach to the risk-informed, performance-based methodology to be used for performing postclosure criticality analyses for waste forms in the Monitored Geologic Repository at Yucca Mountain, Nevada. The risk-informed, performance-based methodology will be used during the licensing process to demonstrate how the potential for postclosure criticality will be limited and to demonstrate that public health and safety are protected against postclosure criticality.
The isotopic composition of mixed-oxide fuel (fabricated with both uranium and plutonium
isotopes) discharged from reactors is of interest to the Fissile Material Disposition Program. The
validation of depletion codes used to predict isotopic compositions of MOX fuel, similar to studies
concerning uranium-only fueled reactors, thus, is very important. The EEI-Westinghouse Plutonium
Recycle Demonstration Program was conducted to examine the use of MOX fuel in the San Onofre
The Reactor and Fuel Cycle Technology Subcommittee was formed to respond to the charge—set forth in the charter of the Blue Ribbon Commission—to evaluate existing fuel cycle technologies and R&D programs in terms of multiple criteria.
In February 1996, the Department of Energy (DOE) commissioned a comprehensive effort to document and declassify the United States inventory and other information needed to present a complete picture of the production, acquisition, and utilization of highly enriched uranium (HEU). Highly Enriched Uranium:Striking A Balance presents the results of that study.
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
The Nuclear Waste Policy Act of 1982, as amended (the Act), assigns the Federal Government the responsibility for the disposal of spent nuclear fuel and high-level waste. Section 302a of the Act authorized the Secretary to enter into contracts with the owners and generators of commercial spent nuclear fuel and or high level waste. The Standard Contract for Disposal of Spent Nuclear Fuel and or High Level Radioactive Waste (Standard Contract) established the contractual mechanism for the Department's acceptance and disposal of spent nuclear fuel and high level waste.
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
This report presents studies to assess reactivity margins and loading curves for pressurized water reactor
(PWR) burnup-credit criticality safety evaluations. The studies are based on a generic high-density 32-
assembly cask and systematically vary individual calculational (depletion and criticality) assumptions to
demonstrate the impact on the predicted effective neutron multiplication factor, keff, and burnup-credit
loading curves. The purpose of this report is to provide a greater understanding of the importance of
Past efforts by the Department of Energy (DOE), the Electric Power Research Institute (EPRI), the Nuclear Regulatory Commission (NRC), and others have provided sufficient technical information to enable the NRC to issue regulatory guidance for implementation of pressurized-water reactor (PWR) burnup credit; however, consideration of only the reactivity change due to the major actinides is recommended in the guidance.
This manual discusses the cost estimating routines used in Version (V) 6.0 of the Total System
Model (TSM) as described in the TSM User Manual (BSC 2007a). The TSM estimates costs
during the simulation of the Civilian Radioactive Waste Management System (CRWMS)
mission. The TSM is not intended to provide a full Total System Life Cycle Cost (TSLCC)
evaluation tool but focuses on the CRWMS Waste Acceptance, Storage, and Transportation
(WAST) elements reported for the TSLCC in Reference BSC 2003a. This manual also
US DOE collaborated with state and tribal stakeholders in the National Transportation Stakeholders Forum (NTSF) Communications ad hoc working group to develop a guide for site personnel to follow when preparing campaign-specific fact sheets.
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
This “Technical Evaluation Report on the Content of the U.S. Department of Energy’s Yucca Mountain License Application; Postclosure Volume: Repository Safety After Permanent Closure” (TER Postclosure Volume) presents information on the NRC staff’s review of DOE’s Safety Analysis Report (SAR), provided on June 3, 2008, as updated by DOE on February 19, 2009. The NRC staff also reviewed information DOE provided in response to NRC staff’s requests for additional information and other information that DOE provided related to the SAR.
The purpose of this calculation report, Range of Applicability and Bias Determination for Postclosure
Criticality of Commercial Spent Nuclear Fuel, is to validate the computational method used to perform
postclosure criticality calculations. The validation process applies the criticality analysis methodology
approach documented in Section 3.5 of the Disposal Criticality Analysis Methodology Topical Report.1
The application systems for this validation consist of waste packages containing transport, aging, and
Fundamentally, a nuclear energy system uses nuclear fission to create heat, which is then available for generating electricity or other applications, including seawater desalination, heating, and production of other fuels. The nuclear energy system as currently deployed in the United States, Figure 1, consists of a number of integrated components, beginning with the natural resources required for nuclear fuel, followed by fissioning of the fuel in reactors connected to electricity generation facilities, and ending with the disposition of all wastes, including used nuclear fuel (UNF).
The Construction Industry Research and Policy Center (CIRPC) at the University of Tennessee was awarded a contract by the Center to Protect Workers’ Rights, under their grant program with the National Institute of Occupational Safety and Health (NIOSH), to analyze injuries of employees of the U. S. Department of Energy (DOE) and their contractors’ working at DOE work sites. The injury data analyzed were injuries recorded in DOE’s Computerized Accident Incident Reporting System (CAIRS).
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013